Selective partitioning of mercury from co-extracted actinides in a simulated acidic ICPP waste stream Metadata

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Title

  • Main Title Selective partitioning of mercury from co-extracted actinides in a simulated acidic ICPP waste stream

Creator

  • Author: Brewer, K.N.
    Creator Type: Personal
  • Author: Herbst, R.S.
    Creator Type: Personal
  • Author: Tranter, T.J.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: USDOE, Washington, DC (United States)

Publisher

  • Name: EG & G, Inc.
    Place of Publication: Idaho Falls, Idaho
    Additional Info: EG and G Idaho, Inc., Idaho Falls, ID (United States)

Date

  • Creation: 1995-12-01

Language

  • English

Description

  • Content Description: The TRUEX process is being evaluated at the Idaho Chemical Processing Plant (ICPP) as a means to partition the actinides from acidic sodium-bearing waste (SBW). The mercury content of this waste averages 1 g/l. Because the chemistry of mercury has not been extensively evaluated in the TRUEX process, mercury was singled out as an element of interest. Radioactive mercury, {sup 203}Hg, was spiked into a simulated solution of SBW containing 1 g/l mercury. Successive extraction batch contacts with the mercury spiked waste simulant and successive scrubbing and stripping batch contacts of the mercury loaded TRUEX solvent (0.2 M CMPO-1.4 M TBP in dodecane) show that mercury will extract into and strip from the solvent. The extraction distribution coefficient for mercury, as HgCl{sub 2} from SBW having a nitric acid concentration of 1.4 M and a chloride concentration of 0.035 M was found to be 3. The stripping distribution coefficient was found to be 0.5 with 5 M HNO{sub 3} and 0.077 with 0.25 M Na{sub 2}CO{sub 3}. An experimental flowsheet was designed from the batch contact tests and tested counter-currently using 5.5 cm centrifugal contactors. Results from the counter-current test show that mercury can be removed from the acidic mixed SBW simulant and recovered separately from the actinides.
  • Physical Description: 15 p.

Subject

  • Keyword: Dodecane
  • Keyword: Sodium
  • Keyword: Actinides
  • Keyword: Radioactive Waste Processing
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Tbp
  • Keyword: Mercury
  • Keyword: Nitric Acid
  • Keyword: Truex Process
  • Keyword: Solvent Extraction
  • Keyword: Mercury 203
  • Keyword: Cmpo

Source

  • Conference: Conference on challenges and innovations in the management of hazardous waste, Washington, DC (United States), 10-12 May 1995

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article

Format

  • Text

Identifier

  • Other: DE96002523
  • Report No.: INEL--95/00243
  • Report No.: CONF-9505164--2
  • Grant Number: FG07-81ID12345
  • Office of Scientific & Technical Information Report Number: 135073
  • Archival Resource Key: ark:/67531/metadc619350

Note

  • Display Note: INIS; OSTI as DE96002523